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WELCOME ADDRESS Lucila Izquierdo General Secretary of External and Institutional Relations CIEMAT Avda. Complutense 22, 28040 Madrid, Spain Ladies and Gentlemen, Dear Michel Hugon, Phillipe Savelli, dear participants, It is my pleasure, as Secretary of External and Institutional Relations of CIEMAT and in the name of its Director General, to welcome all of you to CIEMAT for the 6 th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation. We are glad that Madrid joins the list of cities that have hosted this series of meetings that started in Mito and have got consecutive success at Argonne, Cadarache and Mol. We would like to thank the organisers both NEA/OCDE and the European Commission for their invitation for the joint hosting of the meeting by CIEMAT and ENRESA (the Spanish body for radioactive waste management). CIEMAT is the Spanish Public Organism for Research and Technological Development supported by the Ministry of Science and Technology responsible of finding solutions to improve the use of resources and energy generation systems, to develop alternative energy sources and to solve the problems of the Spanish companies regarding energy and its effects on the environment. CIEMAT is largely involved in the research on future and present nuclear energy sources through the programmes of Nuclear Fusion and Nuclear Fission, whose activities include many projects related to the back-end of the nuclear fuel cycle. At CIEMAT we find in Partitioning and Transmutation (P&T) one very interesting element for the Nuclear Waste management. Ideally, it will allow to achieve large reduction on the inventories of long-lived radioactive wastes contained in the nuclear waste, in particular the actinides, reducing the concerns about our use of nuclear energy for future generations. Not to forget the positive effect on the public acceptance of nuclear waste management programmes and the potential capability to produce huge amounts of electricity. After the participation of CIEMAT in the FEAT and TARC experiments at CERN related to the Energy Amplifier project, already in 1994, the Nuclear Fission Department has initiated a wide P&T research programme in 1997. 17
Page 1 and 2: Nuclear Development ACTINIDE AND FI
Page 3 and 4: FOREWORD The objective of the OECD/
Page 5 and 6: TABLE OF CONTENTS Foreword ........
Page 7 and 8: EXECUTIVE SUMMARY More than 160 par
Page 9: identified. In the fuel area, labor
Page 12 and 13: 17:20-19:05 Session III: Partitioni
Page 14 and 15: Poster sessions Poster session: Par
Page 18 and 19: This programme includes six main li
Page 20 and 21: Laboratory in the USA with the ATW
Page 22 and 23: • Partitioning methods for long-l
Page 25 and 26: SESSION I Overview of National and
Page 27 and 28: collaborative research with foreign
Page 29 and 30: SESSION II The Nuclear Fuel Cycle a
Page 31 and 32: CLOSING THE NUCLEAR FUEL CYCLE: ISS
Page 33 and 34: Relative to the self-sufficient rec
Page 35 and 36: Figure 2. Radiotoxicity of LWR spen
Page 37 and 38: 3.1 Core design constraints In prac
Page 39 and 40: 4. Fuel cycle problems and challeng
Page 41 and 42: Institute of Atomic Research (RIAR)
Page 43 and 44: separation of the uranium from the
Page 45 and 46: Since the radiotoxicity of 129 I is
Page 47 and 48: 8. Summary The principal points and
Page 49: [13] A.V. Bychkov et al., Pyroelect
Page 52 and 53: ecover transuranics for fissioning
Page 54 and 55: 1. Introduction Since the end of th
Page 56 and 57: Am+Cm/Ln(III) separation, (iv) the
Page 58 and 59: • 2 nd step: An(III)/Ln(III) sepa
Page 60 and 61: Technetium ( 99 Tc) The soluble fra
Page 62 and 63: are dissolved by a carbo-chloration
Page 64 and 65: December 1991 Nuclear Waste Act: th
Page 66 and 67:
7 solutions, obtained with the 3 ba
Page 68 and 69:
1. Introduction To give a state-of-
Page 70 and 71:
Table 1. Consequences on the fuel c
Page 72 and 73:
exception of activities started at
Page 74 and 75:
The CONFIRM project, sponsored by t
Page 76 and 77:
Figure 4. A step-by-step approach t
Page 78 and 79:
The major objectives of the MEGAPIE
Page 80 and 81:
Figure 7. The MASURCA installation
Page 82 and 83:
3.3.3 Scenarios studies Scenario st
Page 84 and 85:
4. Major missing points The analysi
Page 86 and 87:
The potential of any fast reactor,
Page 88 and 89:
However, the need to single out a
Page 90 and 91:
REFERENCES [1] M. Salvatores et al.
Page 92 and 93:
[33] A. Puill, J. Bergeron, Advance
Page 95 and 96:
SAFETY CONSIDERATIONS IN DESIGN OF
Page 97 and 98:
The approach taken by the expert gr
Page 99 and 100:
2.2 Safety strategies Strategies to
Page 101 and 102:
composition; this composition depen
Page 103 and 104:
Table 3. Radiotoxicity data (CD = C
Page 105 and 106:
to vary from loading to loading as
Page 107 and 108:
the desired heat rating and on the
Page 109 and 110:
Proton beam transport tube and spal
Page 111 and 112:
Freezing temperatures and coolant/s
Page 113 and 114:
The prompt neutron population estab
Page 115 and 116:
feedbacks successfully exploited an
Page 117 and 118:
[10] a) R.A. Wigeland, Comparison o
Page 119:
POSTER SESSION Partitioning Chair:
Page 122 and 123:
The fourth paper reported on measur
Page 125 and 126:
POSTER SESSION Transmutation System
Page 127:
CD-ROM CONTENTS AND INSTRUCTIONS FO
Page 131 and 132:
RESEARCH AND DEVELOPMENT OF TECHNOL
Page 133 and 134:
The long-term nuclear programme iss
Page 135 and 136:
3.2.3.2 JNC JNC is developing fuel
Page 137 and 138:
4.2 Effects on geological disposal
Page 139 and 140:
design and P&T introduction scenari
Page 141 and 142:
Annex 2 JAERI JNC CRIEPI 141 Elemen
Page 143 and 144:
FRENCH RESEARCH PROGRAMME TO REDUCE
Page 145 and 146:
The procedure involves identifying
Page 147 and 148:
THE STATUS OF THE US ACCELERATOR TR
Page 149 and 150:
of which runs off or is evaporated
Page 151:
REFERENCES [1] A Roadmap for Develo
Page 154 and 155:
1. Introduction In the second half
Page 156 and 157:
the IAEA Departments of Nuclear Ene
Page 158 and 159:
activities is comparison with the a
Page 160 and 161:
17-19 September 1997. Several major
Page 162 and 163:
In spite of the above-mentioned dis
Page 164 and 165:
LIST OF IAEA PUBLICATIONS 1. Intern
Page 166 and 167:
1. Background In 1998 the Research
Page 168 and 169:
form of minor actinides (MAs). Toda
Page 170 and 171:
Figure 2. Time schedule and milesto
Page 172 and 173:
The accelerator of the XADS has not
Page 175 and 176:
PARTITIONING AND TRANSMUTATION IN T
Page 177 and 178:
that would be more economical, safe
Page 179 and 180:
compounds will be studied together
Page 181 and 182:
Table 3. Cluster on transmutation-b
Page 183 and 184:
In view of the future research prog
Page 185 and 186:
ACTIVITIES OF OECD/NEA IN THE FRAME
Page 187 and 188:
2. The previous 10 years The activi
Page 189 and 190:
4. Scientific issues of P&T In para
Page 191 and 192:
This Working Party will envelop the
Page 193 and 194:
• Demonstration Experimental Prog
Page 195:
SESSION II THE NUCLEAR FUEL CYCLE A
Page 198 and 199:
1. Introduction The double-strata f
Page 200 and 201:
Figure 2. Flow-sheet of 4-group par
Page 202 and 203:
from an UO 2 -LWR. The number of tr
Page 204 and 205:
Figure 4. Scenario for development
Page 207 and 208:
TRANSURANICS TRANSMUTATION ON FERTI
Page 209 and 210:
eserved for control bars, shutdown
Page 211 and 212:
Figure 2. Fuel cycle assumed in the
Page 213 and 214:
Reprocessing losses both from the L
Page 215 and 216:
Figure 7: Evolution of k eff of an
Page 217 and 218:
allow to operate for more than 1 20
Page 219 and 220:
ACTINIDE AND FISSION PRODUCT BURNIN
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volume fractions in a wide range co
Page 223 and 224:
equires irradiation times beyond 10
Page 225 and 226:
The dependencies presented allow ma
Page 227 and 228:
Table 3. Different isotope contribu
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Thus, the introduction of an absorb
Page 231 and 232:
Table 9. 107 Pd transmutation effic
Page 233 and 234:
Table 12. 135 Cs transmutation effi
Page 235:
REFERENCES [1] M. Salvatores, I. Sl
Page 238 and 239:
1. Introduction Under the provision
Page 240 and 241:
PWR MIX (MOX with enriched uranium)
Page 242 and 243:
Figure 2. Reduction of potential ra
Page 244 and 245:
REFERENCES [1] Stratégie et progra
Page 246 and 247:
1. Introduction Repository design a
Page 248 and 249:
− − − Waste volume. The quant
Page 250 and 251:
underground in salt domes. The HHRs
Page 252 and 253:
quantity of waste, radionuclide rel
Page 254 and 255:
[7] J.J. Cohen, A.E. Lewis and R.L.
Page 256 and 257:
1. Introduction On 30 December 1991
Page 258 and 259:
Once heated, the salt is entrained
Page 260 and 261:
The salt processing unit includes t
Page 262 and 263:
The volume of salt in the fertile a
Page 264 and 265:
Figure 5. Core mass balance for 0.5
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• As we saw earlier, it offers
Page 269:
SESSION III PARTITIONING SUB-SESSIO
Page 272 and 273:
1. Introduction There is no doubt t
Page 274 and 275:
to be much more ionic than is the c
Page 276 and 277:
Figure 3. One method of the synthes
Page 278 and 279:
REFERENCES [1] Gabriel Y.S. Chan, M
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1. Introduction Radioactive by-prod
Page 282 and 283:
Figure 3. Flowsheet for the hot exp
Page 284 and 285:
Figure 6. Aqueous profiles of fissi
Page 286 and 287:
REFERENCES [1] Z. Kolarik, U. Müll
Page 288 and 289:
1. Introduction Nuclear waste repro
Page 290 and 291:
Figure 3 Cs 2.2 Possibilities of mo
Page 292 and 293:
protonation of [3,3’-Co(1,2-C 2 B
Page 294 and 295:
Figure 8 F O PPh 2 F F F [3] - 6.1
Page 296 and 297:
emarkable the Sr affinity of the fl
Page 299:
SESSION III PARTITIONING SUB-SESSIO
Page 302 and 303:
1. Introduction The present concept
Page 304 and 305:
transuranics will be reduced to the
Page 306 and 307:
REFERENCE [1] A Roadmap for Develop
Page 308 and 309:
1. Introduction Nuclear waste, espe
Page 310 and 311:
Figure 1. Experimental flame fluori
Page 312 and 313:
5. Laboratory research on electrose
Page 315 and 316:
DEMONSTRATION OF PYROMETALLURGICAL
Page 317 and 318:
Figure 1. Experimental test plan of
Page 319 and 320:
Figure 3. Electrorefiner installed
Page 321 and 322:
Figure 6. Recovered Cd-Pu ingot and
Page 323 and 324:
The separation factor (SF(M)) of me
Page 325:
[9] T. Inoue, M. Kurata, L. Koch, J
Page 328 and 329:
1. Introduction Metallic fuel cycle
Page 330 and 331:
The electrorefining apparatus and t
Page 332 and 333:
3.1 Time course of LCC potential an
Page 334 and 335:
3.2 Plutonium concentration depende
Page 336 and 337:
crystallized phase in high density.
Page 338 and 339:
Figure 10. Concept of Pu activity c
Page 340 and 341:
REFERENCES [1] Y.I. Chang, The Inte
Page 343:
SESSION IV BASIC PHYSICS, MATERIALS
Page 347 and 348:
NUCLEAR DATA MEASUREMENTS FOR P&T A
Page 349 and 350:
order to determine σ 0 and I 0 , a
Page 351 and 352:
3.2 Prompt γ-ray spectroscopy For
Page 353 and 354:
REFERENCES [1] H. Harada, H. Watana
Page 355 and 356:
NEW DATA AND MONTE CARLO SIMULATION
Page 357 and 358:
2. General considerations on spalla
Page 359 and 360:
Figure 3. Average neutron multiplic
Page 361 and 362:
4.1 Measurement of residue producti
Page 363 and 364:
Figure 7. Isotopic production cross
Page 365 and 366:
formalism while fission can be desc
Page 367 and 368:
THE MUSE EXPERIMENTS FOR SUB-CRITIC
Page 369 and 370:
The experimental programmes allow t
Page 371 and 372:
The GENEPI accelerator is mainly co
Page 373 and 374:
also experimentally determined usin
Page 375 and 376:
REFERENCES [1] M. Salvatores, M. Ma
Page 377 and 378:
Figure 3. XY loading (at the core m
Page 379 and 380:
OECD/NEA BENCHMARK CALCULATIONS FOR
Page 381 and 382:
The choice of adopting the ALMR ref
Page 383 and 384:
2.1 One-group microscopic cross-sec
Page 385 and 386:
2.2 k eff at beginning of life and
Page 387 and 388:
The burn-up reactivity drop values,
Page 389 and 390:
Figure 7. Axial flux distribution i
Page 391 and 392:
composition at the end of irradiati
Page 393:
REFERENCES [1] OECD/NEA NSC Task Fo
Page 397 and 398:
STAINLESS STEEL CORROSION IN LEAD-B
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Table 1. Specimens were inserted an
Page 401 and 402:
thermocouples placed in the hot zon
Page 403 and 404:
Figure 6. Auger depth profile conce
Page 405 and 406:
chromium concentration values are l
Page 407 and 408:
For high oxygen activity, alloys wi
Page 409 and 410:
6. Conclusions The results obtained
Page 411 and 412:
ACCUMULATION OF ACTIVATION PRODUCTS
Page 413 and 414:
An important radionuclide determini
Page 415 and 416:
Nuclide Table 4. Nuclide concentrat
Page 417 and 418:
THERMAL AND STRESS ANALYSIS OF HYPE
Page 419 and 420:
The target Pb-Bi is coming from the
Page 421 and 422:
Figure 4. Temperature and velocity
Page 423 and 424:
Figure 6. Target geometry for 3-D c
Page 425:
SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Various fuel cycle
Page 430 and 431:
quantities of lanthanide/actinide a
Page 432 and 433:
Figure 4. Densification of MgAl 2 O
Page 434 and 435:
REFERENCES [1] R.J.M. Konings and J
Page 436 and 437:
1. Introduction It is a hard challe
Page 438 and 439:
When recycling Pu but not the minor
Page 440 and 441:
A priori, actinide targets could be
Page 442 and 443:
The deliberate insertion of Am in t
Page 444 and 445:
REFERENCES [1] Th. Maldague et al.,
Page 446 and 447:
1. Introduction The partitioning an
Page 448 and 449:
1 723, 1 823 and 1 923 K in N 2 , N
Page 450 and 451:
A contrast result was also found fo
Page 452 and 453:
Cathodic current was also observed
Page 454 and 455:
On the other hand, the following eq
Page 456 and 457:
REFERENCES [1] Y. Suzuki, T. Ogawa,
Page 459 and 460:
TRANSMUTATION STUDIES IN FRANCE, R&
Page 461 and 462:
concepts for plutonium consumption
Page 463 and 464:
Table 2. Objectives for transmutati
Page 465 and 466:
eing adjusted to take into account
Page 467 and 468:
6.2.1.4 ZrO 2 Due to its low heat c
Page 469 and 470:
Figure 3a. 3D idealised meshing of
Page 471 and 472:
of 5% [24]. The target irradiation
Page 473 and 474:
for the Cochix irradiation (optimis
Page 475 and 476:
• Their high minor actinides (Np,
Page 477 and 478:
REFERENCES [1] P. Bernard, B. Barr
Page 479 and 480:
FISSION PRODUCT TARGET DESIGN FOR H
Page 481 and 482:
2. General description of the core
Page 483 and 484:
3. Basic characteristics of FP tran
Page 485 and 486:
Figure 6. FP target configuration a
Page 487:
Figure 7. Neutron energy spectrum f
Page 491 and 492:
SAFETY ANALYSIS OF NITRIDE FUELS IN
Page 493 and 494:
worth was calculated by removing al
Page 495 and 496:
component increases with pin pitch,
Page 497 and 498:
4. Conclusions Having calculated th
Page 499 and 500:
ASPECTS OF SEVERE ACCIDENTS IN TRAN
Page 501 and 502:
direct cycle gas-cooled fast spectr
Page 503 and 504:
If an inlet blockage occurred in an
Page 505 and 506:
Another innovative approach is part
Page 507 and 508:
REFERENCES [1] US DOE, Generation I
Page 509 and 510:
A SIMPLE MODEL TO EVALUATE THE NATU
Page 511 and 512:
That in steady state conditions bec
Page 513 and 514:
Moreover, the a leg of the assumed
Page 515 and 516:
2.4 The gravitational pull calculat
Page 517 and 518:
Figure 2. The natural convection im
Page 519 and 520:
REFERENCES [1] C. Rubbia et al., Co
Page 521 and 522:
COMPARATIVE STUDY FOR MINOR ACTINID
Page 523 and 524:
nitride fuel, reflection effect of
Page 525 and 526:
Table 3. Core design parameters for
Page 527 and 528:
2.4 Comparison of neutron spectra T
Page 529 and 530:
The vertical and horizontal axes re
Page 531 and 532:
and adjoint flux. Relatively large
Page 533 and 534:
STUDY ON A LEAD-BISMUTH COOLED ACCE
Page 535 and 536:
Proton beam-trip analysis: In an AD
Page 537 and 538:
Figure 2. Temperature change in pri
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4. Lead-bismuth technology Lead-bis
Page 541 and 542:
Figure 4. Schematic cross-section o
Page 543 and 544:
TRANSURANICS ELIMINATION IN AN OPTI
Page 545 and 546:
Figure 2. Main actinides radiotoxic
Page 547 and 548:
Table 1. Fuel composition Isotope D
Page 549 and 550:
Table 3. Average microscopic cross-
Page 551 and 552:
Table 4. Residual fractions of the
Page 553 and 554:
number of C nuclei is near 2 400 ti
Page 555:
[12] Salvatores M., Spiro M., The I
Page 558 and 559:
1. Introduction Accelerator driven
Page 560 and 561:
• The sub-critical nuclear core,
Page 562 and 563:
Figure 3. TRU elimination vs. irrad
Page 564 and 565:
Table 4. General characteristics of
Page 566 and 567:
[9] Rugama Y., Muñoz-Cobo J.L., Va
Page 568 and 569:
1. Introduction SCK•CEN, the Belg
Page 570 and 571:
to 40 to 70 MeV and a booster furth
Page 572 and 573:
2.4 Confinement building Parallel t
Page 574 and 575:
3.2 Spallation source The choice of
Page 576 and 577:
• Ente per le Nuove tecnologie, l
Page 579 and 580:
ADS: STATUS OF THE STUDIES PERFORME
Page 581 and 582:
There is no specific need at the fi
Page 583 and 584:
3.4 The primary coolant and the rea
Page 585 and 586:
these fluids and the insurance of n
Page 587 and 588:
• A solid fuel for the transmutat
Page 589 and 590:
its extended use will not become a
Page 591:
Figure 2. Experimental accelerator
Page 594 and 595:
1. Introduction Nuclear waste can b
Page 596 and 597:
Figure 1. Impact of removing & tran
Page 598 and 599:
epository due to corrosion of the c
Page 600 and 601:
Figure 4. Burn-up of plutonium usin
Page 602 and 603:
accelerator-driven sub-critical mod
Page 604 and 605:
characteristics of this direct (Bra
Page 606 and 607:
The plutonium and minor actinides a
Page 608 and 609:
investigated. Most of the fuel in t
Page 611:
POSTER SESSIONS 611
Page 615 and 616:
STUDIES ON BEHAVIOUR OF SELENIUM AN
Page 617 and 618:
2.2 Chemical speciation The oxidati
Page 619 and 620:
Figure 2. Isothermal equilibrium cu
Page 621 and 622:
Table 2. Influence of aqueous acid
Page 623 and 624:
Figure 7. Influence of HNO 3 concen
Page 625 and 626:
SOLUBILIZATION STUDIES OF RARE EART
Page 627 and 628:
2. Experiment details Cyclic voltam
Page 629 and 630:
Figure 2 (b). Comparison between th
Page 631 and 632:
Activity coefficients of MeCl 3 in
Page 633 and 634:
Table 2. Solubility products, pk s
Page 635 and 636:
the interactions Me-substrate and M
Page 637 and 638:
CALIX[6]ARENES FUNCTIONALISED WITH
Page 639 and 640:
These compounds were reacted with a
Page 641 and 642:
ACTINIDE(III)/LANTHANIDE(III) PARTI
Page 643 and 644:
2. Experimental 2.1 Synthesis and c
Page 645 and 646:
Figure 3. Americium(III) extraction
Page 647:
REFERENCES [1] OECD Nuclear Energy
Page 650 and 651:
1. Introduction Nano- and micropart
Page 652 and 653:
3. Selective removal of histidine-t
Page 654 and 655:
Scheme 6. Formation of the macrocyc
Page 656 and 657:
REFERENCES [1] M.D. Kaminski, and L
Page 659 and 660:
NEW EXTRACTANTS FOR PARTITIONING OF
Page 661 and 662:
of COSAN derivatives allowed for us
Page 663 and 664:
On the other hand, all the above an
Page 665 and 666:
All compounds presented above were
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INFLUENCE OF INTERMEDIATE CHEMICAL
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3. Natural or slightly enriched ura
Page 671:
enrichment 1%, the burn-up grows 1.
Page 674 and 675:
1. Introduction The final disposal
Page 676 and 677:
Table 3. Calculated and experimenta
Page 678 and 679:
Figure 2. General flow-sheet of Tot
Page 680 and 681:
[10] J. Wang, B. Liu, J. Chen, C. S
Page 683 and 684:
DESIGN AND CHARACTERISTICS OF THE n
Page 685 and 686:
The realisation of the present desi
Page 687 and 688:
In the upper right corner of Figure
Page 689 and 690:
Figure 3. Top view of the area wher
Page 691 and 692:
y neutron reactions. The level reac
Page 693 and 694:
The geometry of the beam dump propo
Page 695:
REFERENCES [1] S. Abramovich et al.
Page 698 and 699:
1. Introduction At the dawn of XXI
Page 700 and 701:
The K parameter value, function of
Page 702 and 703:
3. Experimental results The detecto
Page 704 and 705:
Figure 7: Experimental (full line)
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Figure 9. ENDF/B-VI and JEF2.2 simu
Page 708 and 709:
5. Conclusion The neutron capture c
Page 710 and 711:
1. Experimental set-up The charged
Page 712 and 713:
Figure 2. Preliminary results of do
Page 714 and 715:
REFERENCES [1] Alford W.P. and Spic
Page 716 and 717:
1. Introduction For many accelerato
Page 718 and 719:
eam dump. We observe that the major
Page 721 and 722:
INTERMEDIATE ENERGY NEUTRON-INDUCED
Page 723 and 724:
2. Up-to-date status of the (n,f) c
Page 725 and 726:
Figure 2. The 181 Ta(n,f), nat W(n,
Page 727 and 728:
obtained more recently. It is seen
Page 729 and 730:
REFERENCES [1] C. Rubbia, The Energ
Page 731:
[20] P. Staples, P.W. Lisowski, and
Page 734 and 735:
1. Introduction Nuclear fission of
Page 736 and 737:
3. Results and perspectives On the
Page 738 and 739:
Figure 4. Yields of U isotopes in t
Page 741 and 742:
NEUTRON RADIATIVE CAPTURE CROSS-SEC
Page 743 and 744:
15 µA. At the end of the proton be
Page 745 and 746:
conditions with the minimum thermal
Page 747 and 748:
only assumption of the code is that
Page 749 and 750:
4. Conclusions The values of the ne
Page 751 and 752:
DETERMINATION OF THE NEUTRON FISSIO
Page 753 and 754:
Therefore, the neutron induced fiss
Page 755 and 756:
Figure 2. Singles protons and deute
Page 757:
Following the procedure proposed by
Page 760 and 761:
1. Introduction The renewal interes
Page 762 and 763:
Figure 3. Schematic view of a teles
Page 764 and 765:
Figure 6. Calibration curves used f
Page 766 and 767:
Figure 9. Proton spectrum before an
Page 768 and 769:
this energy and the deuteron data o
Page 770 and 771:
absolute values of proton spectra.
Page 772 and 773:
1. Introduction The HINDAS project
Page 774 and 775:
calculated. Moreover, the optical p
Page 776 and 777:
Figure 2. The Berlin ball detector
Page 778 and 779:
Finally, a new experimental techniq
Page 780 and 781:
REFERENCES [1] S. Benck, I. Slypen,
Page 782 and 783:
1. Introduction In Korea, an accele
Page 784 and 785:
Figure 1. Configuration of the Pb-B
Page 786 and 787:
3. Numerical results The performanc
Page 788 and 789:
operation), respectively. This is b
Page 790 and 791:
790 Figure 6. Normalised radial pow
Page 792 and 793:
REFERENCES [1] W.S. Part et al., HY
Page 795 and 796:
MA AND LLFP TRANSMUTATION IN MTRs A
Page 797 and 798:
70 MW. The beryllium matrix has 79
Page 799 and 800:
Table 1. Neutronic design parameter
Page 801 and 802:
Table 3. Target-volume-averaged dir
Page 803 and 804:
Only the fission process allows com
Page 805 and 806:
amounts of MAs. In addition, one sh
Page 807:
[9] E. Malambu, Progress Report on
Page 810 and 811:
1. Introduction In the last years t
Page 812 and 813:
4. Core with zirconium hydride in f
Page 814 and 815:
Figure1. Reference reactor core Fig
Page 816 and 817:
Table 4. Comparison of burn-up para
Page 818 and 819:
8. Power distribution in the refere
Page 820 and 821:
where P r is the reactor power, I p
Page 823 and 824:
REMARKS ON KINETICS PARAMETERS OF A
Page 825 and 826:
2. Sub-critical multiplication The
Page 827 and 828:
Figure 2. Radial flux distribution
Page 829 and 830:
Using such a traditional expression
Page 831 and 832:
NOISE METHOD FOR MONITORING THE SUB
Page 833 and 834:
And the descriptor used in noise an
Page 835 and 836:
Figure 1. Amplitude versus frequenc
Page 837 and 838:
As suggested by Uhrig [6], a method
Page 839:
observed that the precision of the
Page 842 and 843:
1. Introduction Last years importan
Page 844 and 845:
eaches about 0.5% mole at a tempera
Page 846 and 847:
3.2 Precipitation of oxides Althoug
Page 848 and 849:
potentials that must be maintained
Page 850 and 851:
Based on experimental data received
Page 853 and 854:
COMPARATIVE ASSESSMENT OF THE TRANS
Page 855 and 856:
3.1 Reference configuration As in t
Page 857 and 858:
if they are distributed exactly as
Page 859 and 860:
From the perspective of the whole d
Page 861 and 862:
Figure 5. Radial distribution of th
Page 863:
Table 10. Transmutation rates (kg/T
Page 866 and 867:
1. Introduction The concept of a hi
Page 868 and 869:
underground, the radiation field ge
Page 870 and 871:
REFERENCES [1] T. Iwamura et al., R
Page 872 and 873:
Figure 2. Layout of deep undergroun
Page 874 and 875:
1. Introduction The problem of the
Page 876 and 877:
The data presented show that the ra
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1. Introduction The problem of the
Page 880 and 881:
Table 3. Decay heat power of actini
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1. Scientific activity on ADS in wo
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4. Possible technical tasks on crea
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ON NECESSITY OF CREATION OF ACCELER
Page 889 and 890:
Table 2. Transmutation of 99 Tc wit
Page 891:
Another important problem concernin
Page 894 and 895:
1. Introduction During the last yea
Page 896 and 897:
Other original proposal of the indi
Page 898 and 899:
Other original offer about sectiona
Page 900 and 901:
concentration of lead in heavy wate
Page 902 and 903:
[5] Kolesov V.P., Gughovski B.Ya.,
Page 905 and 906:
CONDITIONS OF PLUTONIUM, AMERICIUM
Page 907 and 908:
The further increase after 500 days
Page 909 and 910:
decrease. Total actinide amount muc
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DEMONSTRATION ACCELERATOR DRIVEN CO
Page 913 and 914:
Thus, stable nuclides will be forme
Page 915:
Table 4. Characteristics of linac w
Page 918 and 919:
1. Introduction Nuclear waste radio
Page 920 and 921:
Figure 1. Lengthwise section view o
Page 922 and 923:
Scenario S0. This is our reference
Page 924 and 925:
Scenario 3 shows that mixing of was
Page 926 and 927:
REFERENCES [1] International GT-MHR
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THE USE OF PB-BI EUTECTIC AS THE CO
Page 931 and 932:
P d T = 6.0E+07, time at reactor fu
Page 933 and 934:
The partial differential equations
Page 935 and 936:
Figure 5. Core and heat exchanger p
Page 937 and 938:
with the STAR-CD results is still t
Page 939 and 940:
ONE WAY TO CREATE PROLIFERATION-PRO
Page 941 and 942:
By supposing that FA manufacturing
Page 943 and 944:
exponentially reduces with rather l
Page 945 and 946:
Thus, 232 U generation by only one
Page 947 and 948:
TRANSMUTATION OF LONG-LIVED NUCLIDE
Page 949 and 950:
In the existing open fuel cycle, in
Page 951 and 952:
then include 31% of Np, 66% of Am a
Page 953 and 954:
Let us discuss the radiation balanc
Page 955 and 956:
Higher requirements for the cleanin
Page 957 and 958:
RW disposal is multibarrier configu
Page 960 and 961:
ALSO AVAILABLE ECONOMIC AND TECHNIC
Page 962:
OECD PUBLICATIONS, 2 rue André-Pas
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